b'A P P E N D I X BReactorLast Day of Name Acronym S t a r t u p OperationExperimental Breeder Reactor No. II (continued)to a liquid metal-cooled fast-breeder-reactor power plant. These objectives were met within the first few years of its operation.By September 1969, EBR-II operated at a capacity of 62.5 megawatts and supplied electricity to Argo Westn ne - and the power grid at the Site until its shutdown in 1994. The reactor operated submerged in a tank of liquid sodium coolant. During recycle experiments between 1964-1969, spent fuel was sent by automated handling methods to the Fuel Cycle Facility adjacent to the reactor building, treated by pyrometallurgical techniques, and the useful fissile metal refabricated into new fuel pins.EBR-II also was used to irradiate reactor fuel and structural material samples, testing their durability in breeder-reactor environments. This information helped improve fuel and material performance for future breeder reactors.19. Experimental Organic Cooled Reactor EOCR Never operatedBecause the OMRE (see below) was built as a minimum-cost facility ($1,800,000) to test the feasibility of the organic-cooled reactor concept, it lacked test loops needed to investigate various organic coolants and experimental fuel elements. The EOCR was intended to extend and advance the OMRE studies.During the final stages of its construction, EOCR was placed in standby status in December 1962 when the AEC decided that the organic-cooled concept would not significantly improve nuclear power plant performance over what other reactor concepts already had achieved. The building, located east of the Central Facilities Area, was recycled for other (non-nuclear) uses.20. Fast Spectrum Refractory Metals Reactor 710 March 1962 1968This low-power critical facility operated at TAN to collect data for a proposed fast-spectrum refractory-metal reactor concept called the 710 Reactor.The concept involved using metals such as tungsten and tantalum in a compact, very high-temperature reactor for generating power in space.21. Gas Cooled Reactor Experiment GCRE 2-23-60 4-6-61Built at the Army Reactor Experimental Area, later called the Army Reactor Area (ARA), the GCRE was a wa er -moderated, nitrogen (gas)-cooled, direct- and closed-cycle reactor. It generated 2,200 kilowatts of heat, tbut no electricity. The U.S. Army wanted to develop a mobile nuclear power plant, and the GCRE was the first phase of the program, proving the principle of this reactor concept. The reactor provided engineering and nuclear data for improved components. The GCRE was also used to train military and civilian personnel in the operation and maintenance of gas-cooled reactor systems.22. Heat Transfer Experiment No. 1 HTRE-1 11-4-55 1956Test Area North was opened in 1952 for the Aircraft Nuclear Propulsion program, which operated during the 1950s to develop for the U.S. Air Force a nuclear-powered jet airplane using direct-cycle heat transfer engineering. The program involved ground tests only, but proved the principle of nuclear-powered turbojet engine operation with a full-power test in January 1956, with Heat Transfer Reactor Experiment No. 1 (HTRE-I),which produced 20 megawatts of heat energy on a test stand at TANs Initial Engine Test Facility. The water-moderated reactor used enriched uranium fuel clad in nickel-chromium.23. Heat Transfer Experiment No. 2 HTRE-2 July 1957 3-28-61In order to irradiate fuel elements that were too large to fit in the MTR for materials tests, the ANP program(End of ANPdrilled a hexagonal hole in the center of HTRE-1 and renamed it HTRE-2, converting it to a materials testprogram)reactor and subjecting test fuels to environments reaching 2,800 F. The ANPmaterials test program advanced the technology of high-heat ceramic reactor fuels.263'